RRFM 2009 Transactions - European Nuclear Society

STUDYING OF INFLUENCE OF A NEUTRON IRRADIATION ON
ELEMENT CONTENTS AND STRUCTURES OF ALUMINUM ALLOYS
SAV-1 AND AMG-2
U. S. SALIKHBAEV, S. A. BAYTELESOV, F.R. KUNGUROV
Institute of Nuclear Physics AS RUz
U.Gulomov street, pos. Ulugbek, 100214 Tashkent, Uzbekistan
A. S. SAIDOV
Physical Technical Institute NPO “Fizika-Solntse” AS Ruz
Mavlyanov street, 100084 Tashkent, Uzbekistan
ABSTRACT
It is one of fundamental problems in the sphere of the study of construction
materials for nuclear reactors to create a radiation-resistant material fit for longterm
operation under high-dose neutron radiation conditions. At present, SAV-1
and AMG-2 aluminum alloys are used at the WWR-M reactors as fuel elements
which differ from other alloys with their physical and mechanical properties,
specifically, super-durability, corrosion resistance and high reserve of creepage.
This work is devoted to a study into the influence of neutron radiation on the
elemental composition and structure of the SAV-1 and AMG-2 alloys. With this aim
in view the samples of these alloys were exposed to neutron flux at the WWR-SM
reactor at the Institute of Nuclear of Physics AS RUz, using the fluencies of ≈10 19
neutron/cm 2 .
1.1. Measurement of neutron flux spectrum
• Monitors Au, Co, Ni, Ti, Fe have been made from thin roll flat metal foil, and Y and Mg
were taken in the form of their connections MgO and Y 2 O 3 .
• Two sets of monitors have been weighed, packed into polyethylene packages,
wrapped in aluminum foil and soldered in quartz ampoules. One of ampoules has been
soldered in Cd glass for cut-off by component thermal flux in the course of irradiation of
monitors. Irradiation of both containers was carried out consistently for 2 hours in the
second channel of the reactor general neutrons flux. Measurement of samples’ gamma
activity was carried out in 3-10 days after irradiation. Registration of samples gamma
spectrum was carried out on HP Ge detector with multichannel analyzer DSA1000 of
Canberra firm, processing of gamma spectrum was carried out by means of standard
software package Genie 2000.
% Е threshold , MeV T 1/2 Е, KeV M, mg
197 Au (n, γ) 198 Au 100 2,7 d 5
58 Ni (n, p) 58 Co 67,88 2,6 71,3 d 810,8(99) 12,25
24 Mg (n, p) 24 Na 78,7 6,3 15,05 h 1368,5(100) 1.1457
48 Ti (n, p) 48 Sc 73,94 7 1,83 d 1312,1(100) 15.15
1037,4(100)
983,5(100)
46 Ti (n, p) 46 Sc 7,93 4.5 83,89 d 889,2(100) 15.15
1120,5(100)
54 Fe (n, p) 54 Mn 5,84 3 312,6 d 834,8(100) 9,05
89 Y (n, 2n) 88 Y 100 12 108,1 d 898(92) 5.9842
1836,1(100)
60 Ni (n, p) 60 Co 26,23 6 5,26 y 1173,2(100) 12,25
1332,5(100)
Table 1. Description of monitors
418 of 455
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